27th IEEE Symposium on Fusion Engineering

Session

W.OA1: Materials II

W.OA1

7 Jun 2017, 10:40

Marriott Shanghai City Center

414. Integrating Materials Engineering and Design for Fusion

Dr Michael Gorley (Culham Centre for Fusion Energy)

07/06/2017, 10:40

Materials and fabrication

Invited Oral

The EU-DEMO fusion reactor is facing uncertainty in safety and licencing of in-vessel components that relate directly to the materials and design criteria used for assessments. These challenges come from the designed operation under unprecedented environmental conditions and reliance on the performance of complex in-vessel components over time spans of years. These critical components,...

498. Material Solutions for Flow Channel Inserts for Liquid Metal Blankets

Dr Yutai Katoh (Oak Ridge National Laboratory)

07/06/2017, 11:00

Materials and fabrication

Invited Oral

Flow Channel Inserts (FCI) are key components, originally proposed in European blanket conceptual designs, required in liquid metal-cooled and/or -bred fusion reactor blankets such as the Dual Coolant Lead-Lithium (DCLL) or Helium-Cooled Lead-Lithium (HCLL) concepts. The FCI minimizes the magnetohydrodyamic (MHD) pressure drop and enables higher outlet temperatures for liquid metal than...

129. Effect of Heat Treatment on Anisotropic Tensile Behavior of CLAM Steel Fabricated by Additive Manufacturing

Dr Yutao Zhai (Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)

07/06/2017, 11:20

Materials and fabrication

Oral

Fusion reactor blanket needs to withstand the 14.06 MeV high energy neutron irradiation, high heat flux, high nuclear thermal deposition and complex electromagnetic and mechanical loading and so on, which put forward a high requirement for the structural materials and the quality of components manufacturing. Reduced-activation ferritic/martensitic (RAFM) steel has been developed as the...

392. Synergetic effects of He ions irradiation and oxidation on W

Yi-Ming Lyu (Institute of Plasma Physics, Chinese Academy of Sciences)

07/06/2017, 11:40

Materials and fabrication

Oral

Tungsten (W) is foreseen as one of the most promising plasma facing materials (PFM) of fusion devices. As oxygen exists as a contamination in the vacuum chamber of tokamak, W oxide can form at the surface of W due to good chemical affinity between W and oxygen. W oxide film will inevitably interact with helium (He) ions, which are formed by the deuterium –tritium (D-T) fusion reaction. Many...

479. Tungsten-steel composites fabricated by roll bonding and ultrasonic welding for structural use in plasma-facing components

Lauren Garrison (Oak Ridge National Laboratory)

07/06/2017, 12:00

Materials and fabrication

Oral

Current fusion reactor designs often use a tungsten (W) to copper joint as part of the cooling structure in the plasma-facing components. Future fusion reactors may operate at temperatures above the operating window for copper. Therefore, robust joints between W and advanced steels are desired for fabricating plasma-facing components. A W-steel composite or functionally graded material is...

404. Experiemnt investigation on heat transfer performance enhancement of PFC hypervapotron by micro surface manipulation technology

Prof. Shenghong Huang (supervisor)

07/06/2017, 12:20

Materials and fabrication

Oral

With the progress of ITER and the planned fusion-fission hybrid reactor, there is an urgent need to develop high effective and practical heat-transferring technologies for the removal of extremely high heat fluxes of about 20 MW m-2. Hypervapotron, developed from a subcooled fin enhancement cooling concept, has received widely concerns. With the development of surface manipulation technology...